[1] [1] Carmack J. Fuel development f advanced reacts[R]. Washington DC: Department of Energy, 2016.

[2] [2] Waltar A E, Todd D R, Tsvetkov P V. Fast spectrum reacts[M]. New Yk, USA: Springer, 2012.

[3] [3] Mum J W, Kin H J, Sweidan F B, et al. Metallic fuel perfmance evaluation f micro lead cooled fast react[C]Proceedings of Transactions of the Kean Nuclear Society Virtual Spring Meeting. 2020.

[5] [5] Nuclear Energy Agency. Benchmark f neutronic analysis of sodiumcooled fast react ces with various fuel types ce sizes[R]. NEANSCR(2015)9, 2016.

[6] [6] Hébert A. DRAGON5 DONJON5, the contribution of cole Polytechnique de Montréal to the SALOME platfm[C]Proceedings of the 3rd International Conference on Physics Technology of Reacts Applications. Tetouan, Mocco, 2014.

[7] [7] Sukarno D H. Neutronics analysis of PWR ce using DRAGON, TRIVAC, DONJON computer codes[C]The 2nd International Conference on Energy Sciences (ICES). Bung, Indonesia, 2018.

[8] Al Zain J, El Hajjaji O, El Bardouni T, et al. Deterministic evaluation of safety parameters and neutron flux spectra in the MNSR research reactor using DRAGON-4 code[J]. Journal of Radiation Research and Applied Sciences, 11, 255-261(2018).

[11] Choi H, Choi M, Hon R. Benchmarking DRAGON/PARCS against KRITZ and FFTF measurements[J]. Nuclear Technology, 205, 486-505(2019).

[12] Ponomarev A, Mikityuk K, Zhang Liang, et al. Superphénix benchmark Part I: results of static neutronics[J]. Journal of Nuclear Engineering and Radiation Science, 8, 011320(2022).

[13] Wang Kan, Li Zeguang, She Ding, et al. RMC - a Monte Carlo code for reactor core analysis[J]. Annals of Nuclear Energy, 85, 121-129(2015).

[14] [14] Ponomarev A, Bednarova A, Mikityuk K. New sodium fast react neutronics benchmark[C]Proceeding of PHYS 2018: React Physics Paving the Way Towards Me. Cancun, Mexico, 2018.

[15] [15] Hofman G L, Leibowitz L, Kramer J M, et al. Metallic fuels hbook[R]. Argonne: Argonne National Labaty, 1985.

[16] [16] Nuclear Energy Agency. Hbook on leadbismuth eutectic alloy lead properties, materials compatibility, thermalhydraulics technologies[M]. Nuclear Energy Agency, 2015.

[17] Brown D A, Chadwick M B, Capote R, et al. ENDF/B-VIII. 0: the 8^th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data[J]. Nuclear Data Sheets, 148, 1-142(2018).

[18] Faure B, Marleau G. Simulation of a sodium fast reactor: effect of B₁ leakage models on group constant generation[J]. Annals of Nuclear Energy, 99, 484-494(2017).

[19] Rachamin R, Wemple C, Fridman E. Neutronic analysis of SFR core with HELIOS-2, serpent, and DYN3D codes[J]. Annals of Nuclear Energy, 55, 194-204(2013).

[20] [20] Hebert A, Sekki D, Chambon R. A user guide f DRAGON version5[M]. Canada: cole Polytechnique de Montréal, 2019.